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KEYWORD_EN:boiling 26 result(s) found
 
1. VARIATION OF LOCAL POOL BOILING HEAT TRANSFER COEFFICIENT ON 3-DEGREE INCLINED TUBE SURFACE

KANG MYEONG-GIE
Nuclear Engineering and Technology, vol. 45, iss. 7, 2013, pp. 911-920
 
2. BRIEF REVIEW OF LATEST DIRECT NUMERICAL SIMULATION ON POOL AND FILM BOILING

Kunugi, Tomoaki;
Nuclear Engineering and Technology, vol. 44, iss. 8, 2012, pp. 847-854
 
3. TOWARD MECHANISTIC MODELING OF BOILING HEAT TRANSFER

Podowski, Michael Z.;
Nuclear Engineering and Technology, vol. 44, iss. 8, 2012, pp. 889-896
 
4. CRITICAL HEAT FLUX ENHANCEMENT IN FLOW BOILING OF Al<sub>2</sub>O<sub>3</sub> AND SiC NANOFLUIDS UNDER LOW PRESSURE AND LOW FLOW CONDITIONS

Lee, Seung-Won;Park, Seong-Dae;Kang, Sa-Rah;Kim, Seong-Man;Seo, Han;Lee, Dong-Won;Bang, In-Cheol;
Nuclear Engineering and Technology, vol. 44, iss. 4, 2012, pp. 429-436
 
5. EFFECT OF SOLUBLE ADDITIVES, BORIC ACID (H<sub>3</sub>BO<sub>3</sub>) AND SALT (NaCl), IN POOL BOILING HEAT TRANSFER

Kwark, Sang-M.;Amaya, Miguel;Moon, Hye-Jin;You, Seung-M.;
Nuclear Engineering and Technology, vol. 43, iss. 3, 2011, pp. 195-204
 
6. THE EFFECT OF MICRO/NANOSCALE STRUCTURES ON CHF ENHANCEMENT

Ahn, Ho-Seon;Kim, Moo-Hwan;
Nuclear Engineering and Technology, vol. 43, iss. 3, 2011, pp. 205-216
 
7. NANOTECHNOLOGY FOR ADVANCED NUCLEAR THERMAL-HYDRAULICS AND SAFETY: BOILING AND CONDENSATION

Bang, In-Cheol;Jeong, Ji-Hwan;
Nuclear Engineering and Technology, vol. 43, iss. 3, 2011, pp. 217-242
 
8. MAJOR THERMAL-HYDRAULIC PHENOMENA FOUND DURING ATLAS LBLOCA REFLOOD TESTS FOR AN ADVANCED PRESSURIZED WATER REACTOR APR1400

Park, Hyun-Sik;Choi, Ki-Yong;Cho, Seok;Kang, Kyoung-Ho;Kim, Yeon-Sik;
Nuclear Engineering and Technology, vol. 43, iss. 3, 2011, pp. 257-270
 
9. INHERENT SAFETY ANALYSIS OF THE KALIMER UNDER A LOFA WITH A REDUCED PRIMARY PUMP HALVING TIME

Chang, W.P.;Kwon, Y.M.;Jeong, H.Y.;Suk, S.D.;Lee, Y.B.;
Nuclear Engineering and Technology, vol. 43, iss. 1, 2011, pp. 63-74
 
10. MULTI-SCALE MODELING AND ANALYSIS OF CONVECTIVE BOILING: TOWARDS THE PREDICTION OF CHF IN ROD BUNDLES

Niceno, B.;Sato, Y.;Badillo, A.;Andreani, M.;
Nuclear Engineering and Technology, vol. 42, iss. 6, 2010, pp. 620-635